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Volume 155

Number 1

Hydrogen Production Using High-Temperature Steam Electrolysis Supported by Advanced Gas Reactors with Supercritical CO2 Cycles

Bilge Yildiz, Katherine J. Hohnholt, Mujid S. Kazimi

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 1-21

Technical Paper / Fission Reactors

Evaluation of the Impact of SAMG on the Level-2 PSA Results of a Pressurized Water Reactor

Yu-Chih Ko, Ching-Hui Wu, Min Lee

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 22-33

Technical Paper / Reactor Safety

Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle

T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N. Hill, M. Salvatores, P. J. Finck

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 34-54

Technical Paper / Fuel Cycle and Management

Evaluation of Long-Life Transuranics Breakeven and Burner Cores for Waste Minimization in a PB-GCFR Fuel Cycle

T. A. Taiwo, E. A. Hoffman, R. N. Hill, W. S. Yang

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 55-66

Technical Paper / Fuel Cycle and Management

Feasibility Study on Transient Identification in Nuclear Power Plants Using Support Vector Machines

Christoffer Gottlieb, Vasily Arzhanov, Waclaw Gudowski, Ninos Garis

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 67-77

Technical Paper / Nuclear Plant Operations and Control

Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 78-89

Technical Paper / Nuclear Plant Operations and Control

Thermal Design of an Alternative Boiling Water Reactor Spent Nuclear Fuel Package for Yucca Mountain Repository

P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 90-104

Technical Paper / Radioactive Waste Management and Disposal

Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant

Norihisa Saito, Yumiko Tsuchiya, Seiji Yamamoto, Yoshie Akai, Tadasu Yotsuyanagi, Masafumi Domae, Yosuke Katsumura

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 105-113

Technical Paper / Radioactive Waste Management and Disposal

Chronic Dose Due to a Continuous Tritium Release Calculated by CAP88-PC and NORMTRI

Stacey F. Imboden, Thomas J. Overcamp

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 114-118

Technical Note / Radiation Protection

 
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